Evaluation of codisposal viability of MOX (FFTF) DOE-owned fuel: Phase 2 -- Degraded mode calculations
The authors provide the degraded criticality information that supports the disposal of spent nuclear fuel (SNF) from the US Department of Energy's (DOE's) Fast Flux Test facility (FFTF) in the potential Monitored Geologic Repository (MGR) at Yucca Mountain. FFTF is one of more than 250 forms of DOE-owned SNF. Because of the variety of the SNF, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The FFTF fuel is a mixture of uranium and plutonium oxides and is representative of the mixed-oxide fuel (MOX) group. The analyses were performed according to the disposal criticality analysis methodology that was documented in the topical report submitted to the US nuclear Regulatory Commission (YMP/TR-004Q). The methodology includes analyzing the geochemical and physical processes that can breach the waste package and degrade the waste forms. This paper summarizes the results of geochemistry degradation analysis and the criticality calculations using the degradation products.
- OSTI ID:
- 20005782
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 81; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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